6 Matching Results

Search Results

Advanced search parameters have been applied.

MIT LMFBR blanket research project. Quarterly progress report, April 1-June 30, 1979

Description: In designing a plutonium-uranium core with thorium internal blankets there are several parameters that must be investigated to identify the design with the best performance. Choices include: the amount of moderation in the blanket, whether moderation is incorporated from the outset or added after an assembly is shuffled to the external blanket, and the cycle length both for the core and internal blanket assemblies. To investigate the effect of these parameters several core and blanket burnup analyses were performed.
Date: July 25, 1979
Creator: Driscoll, M.J.
Partner: UNT Libraries Government Documents Department

LMFBR safety program. Quarterly technical progress report, October-December 1976

Description: Information related to sodium fires and fission products in LMFBR type reactors is presented concerning SOMIX code development; sodium jet dispersal tests; aerosol leakage; high temperature-concentration aerosol tests; aerosol source term size; and properties of high temperature fuel mixtures.
Date: February 25, 1977
Creator: Heisler, M.P.; Johnson, R.P.; Nelson, C.T.; Vaughan, E.U.; Guderjahn, C. & Eytel, L.
Partner: UNT Libraries Government Documents Department

Partitioning and transmutation: Near-term solution or long-term option?

Description: Starting in 1989, the concept that partitioning and transmuting actinides from spent nuclear fuel could be a {open_quotes}solution{close_quotes} to the apparent lack of progress in the high-level waste disposal program began to be heard from a variety of sources, both in the US and internationally. There have been numerous papers and sessions at scientific conferences and several conferences devoted to this subject in the last three years. At the request of the US Department of Energy, the National Research Council is evaluating the feasibility of this concept. Because either plutonium or highly enriched uranium is needed to startup breeder reactors, there is a sound rationale for using Pu from reprocessing spent light-water reactor fuel to start a conversion to Pu-breeding liquid metal reactors (LMRs), once society makes the determination that adding a large component of LMRs to the electricity-generating grid is desirable. This is the long-term option referred to in the title. It is compatible with the current and likely future high-level waste program, as well as the current nuclear power industry in the US. However, the thesis of this paper is that partitioning and transmutation (P-T) does not offer a near term solution to high-level waste disposal in the US for numerous reasons, the most important of which is that a repository will be needed even with P-T. Other important reasons include: (1) lack of evidence that the public will be more likely to accept a repository that has a reduced inventory, (2) the waste disposal program delays do not result from technical evidence of lack of safety, (3) the economics of reprocessing and/or P-T are unfavorable, and (4) obtaining the benefits from P-T requires a long-term commitment to nuclear power.
Date: February 25, 1993
Creator: Ramspott, L. D. & Isaacs, T.
Partner: UNT Libraries Government Documents Department